Transmutation Reactor Research Articles

Evidence that Femto-H2 Exists Leads to the Correct Mechanism of Cold Fusion (Cold Fusion is Caused by Femto-D2)

Femto-H2 is generated by compression of H- H bond of H2 confined at expandable T site, and authors’ mechanism of Cold fusion is that femto-D2 created at expandable T site cause fusion of D+D due to the shielding of coulomb repulsive force because femto- D2 has so dense electron between d-d that coulomb repulsive force is shielded to cause Fusion. One of the controversial heat generation reactors is QHe (Quantum Hydrogen Energy) developed by clean-planet, who explains that QHe is a heat-generating technology with hydrogen quantum diffusion. The diffusion is induced by heating a small amount of hydrogen saturated in nano-sized nickel-based composite material. Although they did not describe it cold fusion, it is commonly understood to be cold fusion. Therefore, this kind of Cold fusion debate is so confusing that no common standard theory has been established. Therefore, I would like to explain the mechanism of QHe based on author’s Mechanism of Cold Fusion. with H2 loading into multi-stacked Ni/Cu which has large number of reaction site of grain-boundary, where the hydrogen segregates to enhance the reaction of femto- H2 generation. And femto-H2 can fuse to Cu or Ni to be mainly Ze to generate 15~17MeV, which is comparable of energy by D+D=4He+24MeV.Because femto-H2 is so small to fuse to the metal nucleus at room temperature, and at high temperature, the nucleus vibrates at high speed and femto-H2 can fuse with the metal nucleus and once the heat generation start transmutation continues. Author also discovered phenomena that seems to be related to femto-H2, which are transmutation reactor by Dr. Ohmasa and car on H2O (Water Fuel CELL) by Stanly A Meyer. Ohmasa’s transmutation reactor uses Pd coating plate and loaded hydrogen by electrolysis generate femto-H2 which enter into H2O to transmute H2O to be helium-3 and oxygen-18 clusters. Water Fuel Cell can generate huge heat by the transmutation of metal with femto-H2. Therefore, author would like to request clean-planet to study the transmutation with femto-H2 in QHe reactor to prove author’s mechanism hypo, and Cold fusion community to start the discussion on the standard theory of Cold Fusion because author’s mechanism is inconsistent with nucleus model.

Conceptualized Fusion Reactor based on Gas Turbine with High Temperature CO2

Author discovered the mechanism of Cold fusion that covalent bond compression of D-D transition electron to deep orbit which distance is a few femto- meters from the nucleus, which electron density between d-d is so dense that it shields the coulomb repulsive force to cause Fusion, and discovered that nucleus is constituted only by proton and internal electron and neutron is a pair of proton and electron in deep orbit. Dr. Ohmasa claims that his transmutation reactor produce produces precious metal from base metal, which shows experimentally and author discovered that femto-H2 fusion to metal cause transmutation, which proves the existence of femto-H2, and femto-D2 therefore current nucleus model is probed to be incorrect. Dr. Ohmasa also claims that CO2 can be reduced by burning with fossil gas fuel mixed with H2 and O2, and author hypothesized the cause that compression of C-O bond cause fusion between C and O to be P and Si based on the correct nucleus model and based on author’s Cold fusion mechanism of bond compression. Developing this mechanism and hypothesis, I would like to propose the conceptualized fusion reactor based on gas turbine with high temperature CO2. D-D bond can be compressed by high temperature CO2 and by the collision of high-speed blades in gas turbine to cause D+D fusion and C+O fusion, which reduce the CO2 emission. Reactor needs to be cooling to generate power by steam turbine and high- speed blade rotation produce power and causes fusions.

The influence of source locations of different multi-beam concept on the power density distribution and nuclear waste transmutation performance for ADS–NWT

The multi-beam concept for the accelerator driven subcritical reactor (ADS) has the advantages in reducing the requirements for the accelerator and can flatten the power distribution of the core. However, the layout of the multi-beam should meet the goal of balancing the relationship between the total power density, the neutron leakage, and the nuclear waste transmutation performance. For the further study of the multi-beam concept for the ADS, this paper focuses on the influence of the source locations of different multi-beam concept on the power density distribution, the neutron leakage, and the nuclear waste transmutation performance for the ADS for a nuclear waste transmutation reactor (ADS–NWT). The different variations on the radial power density distribution and the nuclear waste transmutation performance for the three-, four-, six-, and seven-beam concept for ADS–NWT were analyzed. The results show that the related neutronics performance for the multi-beam concept for ADS-NWT is not only affected by the external source locations and the core geometry, but also affected by the keff and the interference effect between the spallation targets. Moreover, the fission reaction ratio and the fission reaction / (n, gamma) absorbtion ratio for minor actinides (MA) and plutonium (Pu) for the few beams concept are both higher than that for the many beams concept. Based on the analysis of the influence of source locations on the neutron spectrum, the total neutron flux, and the nuclear waste transmutation performance for MA and Pu, the related conclusions about how to arrange the best beam position from the perspective of nuclear waste transmutation and production capacity are provided.

Optimal Radial Build and Transmutation Properties of a Fusion-Based Transmutation Reactor with Molten Salt Coolants

The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements. System parameters such as neutron multiplication, power density, shielding, and tritium breeding, were calculated in a self-consistent manner by coupling neutron transport analysis with conventional tokamak systems analysis. The plasma physics and engineering levels were similar to those used in the International Thermonuclear Experimental Reactor. The influence of aspect ratio of the tokamak and fusion power on the radial build, and the transmutation properties associated with two molten salt options, FLiBe and FliNaBe, were investigated. Being compared with a transmutation reactor with a small aspect ratio, a transmutation reactor with large aspect ratio was smaller in size and had a larger maximum fusion power. This type of reactor also revealed increased tritium-breeding capability and a smaller initial transuranic (TRU) inventory with a slightly lower burn-up rate. The burn-up rate for molten salt using either FLiBe or FLiNaBe was similar, but the initial TRU inventory and the tritium-breeding capability were smaller with FLiNaBe compared with FLiBe.

Conceptualized Transmutation Reactor based on Cold Fusion Mechanism (Possibility of Transmutation to Superheavy Element by Cold Fusion Mechanism)

Conceptualized Transmutation Reactor based on Cold Fusion Mechanism (Possibility of Transmutation to Superheavy Element by Cold Fusion Mechanism)

Classical Physics-based Renewable and Sustainable Energy Transition Concept

By many accounts, Lorentz was ahead of his time by suggesting before quantum mechanics that some disturbances, like waves, travel with particles through a vacuum without moving it. The waves associated with the Lorentz metrics are described by the Klein-Gordon equation and dispersion relation w²=c²k²+w_c². In hydromechanics, they are known as non-propagating waves and w_c is a constant called the cutoff frequency. The waves are not propagating if their frequency is below the cutoff frequency w_c. Their group and phase velocity are related by vu=c², in the infinite k limit v=u=c. A quantum object is considered as a particle moving in resonance with wave characterized by the Klein-Gordon dispersion relation with cutoff or Compton frequencyw_c=mc²/ħ. This approach brings field values (group velocity and intensity of transverse non-propagating waves) into Maxwell's equations, and antiparticles or non-propagating waves with negative group velocity into Newtonian mechanics. In classical astrophysics, matter-antimatter interactions led to the universe expansion, formation of galaxiesand sources of intense cosmic radiation. Classical field theory could play a major role in clean energy research. In particular, concentrating solar power (CSP) systems, i.e. Stirling engine (SE) or small direct-heated tower, with thermal energy storage (TES), diffuse light-utilizing photovoltaic (PV) cell and 3D-printed thermal field emission (TFE) converters will dramatically lower the cost and energy payback time of the CSP technologies. The design explores recent developments in field-effect PV cells. 3D-printed TFE panels-integrated in TES or micro-channel solar receivers. The improved performance of the TFE converter compared to photovoltaic cells at high temperatures is attributed to the simultaneous use of diffusion and ballistic electron transport to harvest both thermal and photon energy. In addition, a gas cooled water moderated reactor is explored to integrate electrical-in-nature nuclear energy into smart micro-grids. and convert the most hazardous wastes into an emission-free fuel and medical isotopes. Transmutation reactor, in which depleted uranium acts initially as an absorber and later as fuel, behaves like fast reactors, but without their difficult control problems and high fissile fuel load.

Estimation of uncertainty in transmutation rates of LLFPs in a fast reactor transmutation system via an estimation of the cross-section covariances

ABSTRACT A new concept of transmutation system for six long-lived fission products (LLFPs: 79Se, 93Zr, 99Tc, 107Pd, 129I, and 135Cs) consisting of three small-size fast reactor cores was proposed. In order to establish a method to estimate the effects of cross-section uncertainties on the transmutation rates of the LLFPs, cross section covariances for the six LLFPs were estimated using a T6 system which includes resonance and statistical models via propagation of model uncertainties, and the uncertainties of transmutation rates and support factors of the six LLFPs in the three fast reactors were estimated based on a Total Monte Carlo (TMC) method. It was made clear that some of the transmutation rates of these LLFPs have large uncertainties indicating that the accuracy of cross sections for them is not enough, and hence the strategy for efficient transmutation may have to be reconstructed. It is concluded that the T6 system and the TMC method used in this study are quite effective not only to estimate the uncertainties of cross sections but also to assess the effect of error propagation throughout the series of calculations conducting in this study.

The main problems of transmutation of actinides and long-lived fission products from NPP spent fuel

The paper formulates the main problems associated with research on transmutation, which should be paid attention to by today’s young researchers. The processes of production of hazardous nuclides during transmutation in reactor facilities are considered. The goals of transmutation and the choice of nuclides to be transmuted are discussed. The concept of radiotoxicity is explained as a measure of the radiological hazard of radioactive nuclides, based on the maximum permissible concentration of nuclides according to the IAEA standards. The problem of the formation of secondary radioactive nuclides in nuclear fuel during generation of neutrons for transmutation is discussed. The advantages and disadvantages of various methods of transmutation in nuclear installations are considered: inclusion of transmutable nuclides in nuclear fuel in fast reactors, transmutation in specialized thermal and fast transmutation reactor installations and ADS systems. The problem of accumulation of highly radioactive actinides in a transmutation facility during long-term transmutation and the problem of a potential hazard of the transmutation facility itself are discussed. The unacceptability of application of common-type power reactors for the transmutation of long-lived fission products is demonstrated.

Investigation of radiation levels in the region of fuel-transfer cask for transportation of spent fuel of light-water reactors

The paper formulates the main problems associated with research on transmutation, which should be paid attention to by today’s young researchers. The processes of production of hazardous nuclides during transmutation in reactor facilities are considered. The goals of transmutation and the choice of nuclides to be transmuted are discussed. The concept of radiotoxicity is explained as a measure of the radiological hazard of radioactive nuclides, based on the maximum permissible concentration of nuclides according to the IAEA standards. The problem of the formation of secondary radioactive nuclides in nuclear fuel during generation of neutrons for transmutation is discussed. The advantages and disadvantages of various methods of transmutation in nuclear installations are considered: inclusion of transmutable nuclides in nuclear fuel in fast reactors, transmutation in specialized thermal and fast transmutation reactor installations and ADS systems. The problem of accumulation of highly radioactive actinides in a transmutation facility during long-term transmutation and the problem of a potential hazard of the transmutation facility itself are discussed. The unacceptability of application of common-type power reactors for the transmutation of long-lived fission products is demonstrated.

Possibility of Burning Americium in Fast Reactors

The possibilities of burning americium from spent nuclear fuel of thermal reactors in the operating BN-800 are examined. It is shown that because of the small fission cross-section in the neutron spectrum of a fast reactor all of the americium cannot be directly converted into fission products. This can be done only by transmutation of americium into plutonium, which must be separated and directed into fuel, where it will burn. In a reactor only 15–20% of the americium is transmuted, and the remaining americium must be returned into the reactor for transmutation. The volume of the recycled americium can be significantly reduced by burning in facilities possessing a moderator (zirconium hydride) and the need for burning it can be eliminated by using plutonium with a high content of the isotope 241Pu as the fuel of fast reactors, where this isotope fissions efficiently.

A fast reactor transmutation system for 6 LLFP nuclides

A fast reactor transmutation system with enhanced transmutation efficiency for six long-lived fission products (LLFP: 79Se, 93Zr, 99Tc, 107Pd, 129I, and 135Cs) was evaluated. A new fast reactor transmutation system concept consisting of three fast reactor cores was constructed by loading six LLFP nuclides on a radial blanket, axial blanket and shield using YD2 and YH2 moderators. By combining three MONJU-class fast reactors, the ratio of the amount of transmuted nuclides in the three reactors to the amount of nuclides produced in the three reactors were achieved 1 or more for all six LLFP nuclides, and the effective half-lives were significantly reduced.

Проблема оптимального выделения америция из ОЯТ БРЕСТ-ОД-300 на трансмутацию для обеспечения радиационной эквивалентности РАО и природного урана

Проблема оптимального выделения америция из ОЯТ БРЕСТ-ОД-300 на трансмутацию для обеспечения радиационной эквивалентности РАО и природного урана

Design of an accelerator-driven subcritical dual fluid reactor for transmutation of actinides

An accelerator-driven subcritical dual fluid reactor (AD-DFR), which is a hybrid core operated by a high power accelerator, is designed for the transmutation of minor actinides. The subcritical core is dual in the sense that a lead-bismuth-eutectic-cooled fast reactor (LFR) is combined with a molten salt reactor (MSR). Thus, the core has two loops: one for the liquid metal coolant and the other for the molten salt fuel. The combination of LFR and MSR can take advantages of both reactor types. A subcritical core allows for loading a high fraction of minor actinides in fuels. An 800MW_t AD-DFR can transmute minor actinides approximately 120kg/year with only the maximum beam power of 13MW.

ОСНОВНЫЕ ПРОБЛЕМЫ ОБРАЩЕНИЯ С РАДИОАКТИВНЫМИ ОТХОДАМИ ИЗ ОТРАБОТАВШЕГО ТОПЛИВА АЭС С ПРИМЕНЕНИЕМ ЯДЕРНОЙ ТРАНСМУТАЦИИ

the main problems associated with research on transmutation, and whichshould be paid attention to by today's young researchers, are formulated. The processes of formation of hazardous nuclides during transmutation in reactor facilities are considered. The goals of transmutation and the choice of nuclides to be transmuted are discussed. The concept of radiotoxicity is explained as a measure of the radiological hazard of radio-active nuclides, based on the maximum permissible concentration of nuclides according to the IAEA standards. The problem of the formation of secondary radioactive nuclides in nuclear fuel during generation of neutrons for transmutation is discussed. The advantages and disadvantages of various methods of transmutation in nuclear installations are con-sidered: inclusion of transmutable nuclides in nuclear fuel in fast reactors, transmutation in specialized thermal and fast transmutation reactor installations and ADS systems. The problem of the accumulation of highly radioactive actinides in a transmutation installa-tion during long-term transmutation and potential hazard of the transmutation instal-lation itself is discussed. The unacceptability of the use of serial nuclear reactors for the transmutation of long-lived fission products has been shown.

Evaluation on transmutation of minor actinides discharged from PWR spent fuel in the RSG-GAS research reactor

The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its effectiveness to transmute minor actinides (MA), specifically Am-241, to support geologic storage/disposal. The Am-241 radionuclide was assumed to be discharged from 1000MWe PWR’s spent fuel. The mass of Am-241 discharged from within a year operation of 1000MWe PWR was 1.65E+03 gram, while the optimum Am-241 mass which can be transmuted in RSG-GAS - and still meet the safety requirements of reactivity - was 8.0E+03 gram. This was equivalent to about cumulative Am-241 discharged from 5 units of 1000MWe PWR. In 10 cycles of RSG-GAS operation (about 2 years), the remaining of Am-241 is only about 100 grams. The ratio of Am-241 transmuted (8.0E+03 gram) and Am-241 produced in the RSG-GAS core (1.98E-02 gram) within 1-year operation shows the effectiveness of RSG-GAS as a transmutation reactor.

Effect of tokamak neutron source shape on radwaste transmutation

The effects of tokamak neutron source shape on the radial build and transmutation characteristics of a transmutation reactor were investigated. The optimal dimension of the reactor components was determined by the requirements not only on plasma physics and tokamak engineering, but also on neutronic performance. Tokamak neutron source shapes with two aspect ratios and two blanket configurations were compared. With the plasma physics and tokamak engineering constraints moderately extrapolated from the International Thermonuclear Experimental Reactor (ITER) design, the transmutation reactor with a normal aspect ratio (NAR) tokamak neutron source showed better transmutation performance with a smaller system dimension and larger fusion power than a low aspect ratio (LAR) tokamak neutron source. It was also shown that, with separate TRU burning and tritium breeding blanket configuration, the transmutation ratio was larger with the smaller initial TRU inventory than with merged TRU burning and tritium breeding blanket configuration.

The development of neutron-physical model for two-zone research suhcritical reactor for nuclear waste transmutation

The development of neutron-physical model for two-zone research suhcritical reactor for nuclear waste transmutation

Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor

A configuration of a fusion-driven transmutation reactor with a low aspect ratio tokamak-type neutron source was determined in a self-consistent manner by using coupled analysis of tokamak systems and neutron transport. We investigated the impact of blanket configuration on the characteristics of a fusion-driven transmutation reactor. It was shown that by merging the TRU burning blanket and tritium breeding blanket, which uses PbLi as the tritium breeding material and as coolant, effective transmutation is possible. The TRU transmutation capability can be improved with a reduced blanket thickness, and fast fluence at the first wall can be reduced. Article History: Received: July 10th 2017; Received: Dec 17th 2017; Accepted: February 2nd 2018; Available onlineHow to Cite This Article: Hong, B.G. (2018) Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor. International Journal of Renewable Energy Development, 7(1), 65-70.https://doi.org/10.14710/ijred.7.1.65-70

Minor actinide transmutation characteristics in AP1000

We study the minor actinide transmutation characteristics by coating different thickness minor actinide on fuel pellets of the AP1000. The calculation results indicate that the more minor actinide is loaded to AP1000, the more boric acid concentration need to be reduced from coolant to let keff return criticality. The relationship between the reduced boric acid concentrations in AP1000 coolant with minor actinide loading amount is not linear. The reduced boric acid concentration in coolant approaches a saturation level after about 300.0 kg minor actinide loading amount. This implies that too much minor actinide loading amount in a single AP1000 fuel loading is meaningless.Our simulation results also denote that loading minor actinide to AP1000 core does affect the power distribution of AP1000 in some way, we need to reduce the boric acid concentration and rearrange the burnable poison rods in the core simultaneously to achieve the purpose of flatting the power distribution. So a moderate minor actinide loading in AP1000 will not adversely affect the core power distribution strikingly.Our calculation results also display that fuel temperature coefficient (FTC) is still negative after adding minor actinide to reactor. In comparison with the standard AP1000 reactor core, the extent of the negative feedback effect of FTC after loading minor actinides is reduced to some extent; the moderator temperature coefficient (MTC) improves the negative feedback effect of the reactor core to a great extent. Taking into account all analytical results about FTC and MTC, the total negative feedback effect on reactor power level changes is improved after loading minor actinides to AP1000 reactor for transmutation. The transmutation rate calculation results show that AP1000 reactor can incinerate 44.0 kg MA nuclides after one year fuel cycle. So AP1000 reactor can incinerate almost 2 times the annual MA yield from a typical PWR reactor.

Dynamic Safety Analysis of a Subcritical Advanced Burner Reactor

A customized dynamic safety model is developed and used to analyze the safety characteristics of the Subcritical Advanced Burner Reactor (SABR), a fast transmutation reactor driven by a tokamak fusion neutron source. Loss-of-flow accidents (LOFAs), loss–of–heat sink accidents (LOHSAs), and loss-of-power accidents (LOPAs) are analyzed taking into account the effects of feedback mechanisms, control rod insertion, and terminating electrical power to the neutron source. The core avoids fuel melting and coolant boiling without corrective action for 50% (failure of one of two pumps) loss of heat sink (LOHSA) and loss of flow (LOFA). For 100% (failure of both pumps) LOFAs, LOHSAs, and LOPAs without corrective action, coolant boiling (1156 K)/fuel melting (1473 K) occur at about 25 s/36 s, 35 s/84 s, and 25 s/36 s, respectively, after pump failure unless corrective control action is taken before this time, in which case the core power can be reduced to the decay heat level by shutting off the plasma power source. The present passive heat removal system is not sufficient to remove the decay heat, and both fuel melting and coolant boiling ultimately occur in the 100% LOFAs and LOHSAs (failure of both pumps) in either the primary or secondary system indicating the need to provide other means for decay heat removal.